ML20213F124

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Concurs W/Intent of Amend 108 to License DPR-16,revising Radiological Effluent Tech Specs,Per 10CFR50,App I.Exception Taken to Basis 3.6.A (SEP Topic XV-16) Re Radiological Consequences
ML20213F124
Person / Time
Site: Oyster Creek
Issue date: 11/07/1986
From: Scott D
NEW JERSEY, STATE OF
To: Zwolinski J
Office of Nuclear Reactor Regulation
References
TASK-15-16, TASK-RR TAC-08100, TAC-8100, NUDOCS 8611140022
Download: ML20213F124 (1)


Text

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y DEPARTMENT OF ENVIRONMENTAL PROTECTION DIVISION OF ENVIRONMENTAL QUALITY BUREAU OF NUCLEAR ENGINEERING CN 411 TRENTON, NEW JERSEY 08625 (609) 530-4022 November 7, 1986 Mr. John A. Zwolinski, Director BWR Project Directorate #1 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Zwolinski:

SUBJECT:

LICENSE AMENDMENT NO. 108 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION (MPA A-02, TSCR 69, TAC 08100)

Re: Oyster Creek Nuclear Generating Station The Bureau staff reviewing this license amendment has advised me that we have concurred with the intent of Amendment No. 108, which authorizes changes to Appendix A technical specifications to incorporate the Radiological Effluent Technical Specifications (RETS) required by 10CFR50 Appendix I. They do however, take exception to Basis 3.6.A (SEP Topic XV-16: Radiological Consequences of Failure of Small Lines Carrying Primary Coolant Activity Outside Containment) as it impacts on federal regulations, i.e. 10CFR100. As they have discussed with Mr.

Donohew by telephone, my staff has specific concerns with the licensee's ability te mitigate this type of accident due to the unique desige of Oyster Creek.

I understand that this component has been eliminated from this licensing action and will be addressed separately in license No. DPR-16 (Postulated High Energy Line Break within Emergency Condenser Penetrations). Mr. Tosch has asked me to request more technical information on SEP Topic XV-16, i.e. the essumptions on which the Safety Evaluation Report's conclusions were based.

I If you should have any questions, please contact Mr. Kent Tosch, of my staff, at (609) 530-4022. (

Thank you.

10 Very truly yours,

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8611140022 861107 9 n /

[//, (fy PDR ADOCK 0500 (f P David'M. Scott, Chief Bureau of Nuclear Engineering pOb cc: Gerald P. Nicholls, Ph.D.

Jack Donohew, NRR A0 b' , i Kent Tosch